Break spectrum analyses for small break loss of coolant accidents in a RESAR-3S Plant [electronic resource].

Published:: Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1986.
Physical Description:: Pages: 74 : digital, PDF file
Additional Creators:: United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

A series of thermal-hydraulic analyses were performed to investigate phenomena occurring during small break loss-of-coolant-accident (LOCA) sequences in a RESAR-3S pressurized water reactor. The analysis included simulations of plant behavior using the TRAC-PF1 and RELAP5/MOD2 computer codes. Series of calculations were performed using both codes for different break sizes. The analyses presented here also served an audit function in that the results shown here were used by the US Nuclear Regulatory Commission (NRC) as an independent confirmation of similar analyses performed by Westinghouse Electric Company using another computer code. 10 refs., 62 figs., 14 tabs.

Report Numbers:

E 1.99:nureg/cr-4384
E 1.99: egg-2416
egg-2416
nureg/cr-4384

Subject(s):

Note:

Published through SciTech Connect.
03/01/1986.
"nureg/cr-4384"
" egg-2416"
"TI86009059"
Fletcher, C D; Kullberg, C M.
EG and G Idaho, Inc., Idaho Falls (USA)

Funding Information:

AC07-76ID01570

View MARC record | catkey: 23781979